ML20239A195
| ML20239A195 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/31/1998 |
| From: | Williams J NRC (Affiliation Not Assigned) |
| To: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-MA1764, NUDOCS 9809080309 | |
| Download: ML20239A195 (6) | |
Text
Mr. J mes Knubel
~ August 31, 1998 Chief Nuclear Officer Power Authority of tha Stria of New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD BOLTING RELIEF REQUEST (TAC NO. MA1764)
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Dear Mr. Knubel:
1 On May 8,1998, the New York Power Authority (also known as the Power Authority of the State of Now York) submitted a request for relief from inservice inspection requirements for control rod bolting at the James A. FitzPatrick Nuclear Power Plant. The NRC staff, with the assistance of its contractor, INEEL, has determined that additional information will be required to complete its review of this relief request. The information required is described in the enclosure to this letter.
To expedite the review process, please provide a copy of your response directly to INEEL at the following address:
MichaelT. Anderson
' INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 As discussed with Mr. Art Zaremba on August 27,1998, please provide the requested information by September 14,1998. If you have any questions regarding this matter, please contact me at (301) 415-1470.
Sincerely, original signed by:
I Joseph F. Williams, Project Manager
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Project Directorate 1-1 Division of Reactor Projects - 1/11 j
9909090309 990831 Office of Nuclear Reactor Regulation I
PDR ADOCK 05000333 O
PDR Docket No. 50-333
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Mr. James Knubel August 31, 1998 p
Chi:f Nucie:r Officer a
l Power Authority of the Stat 3 of j
New York i
123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD BOLTING RELIEF REQUEST (TAC NO. MA1764)
Dear Mr. Knubel:
On May 8,1998, the New York Power Authority (also known as the Power Authority of the State of New York) submitted a request for relief from inservice inspection requirements for control rod botting at the James A. FitzPatrick Nuclear Power Plant. The NRC staff, with the assistance of its contractor, INEEL, has determined that additional information will be required to complete its review of this relief request. The information required is described in the enclosure to this letter.
To expedite the review process, please provide a copy of your response directly to INEEL at the j
following address:
MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 As discussed with Mr. Art Zaremba on August 27,1998, please provide the requested information by September 14,1998. If you have any questions regarding this matter, please contact me at (301) 4151470.
Sincerely, original signed by:
Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Request for Additional Information i
I cc w/ encl: See next page DISTRIBUTION.
l Docket File J. Zwolinski J. Williams C. Hehl, Region i PUBLIC S. Bajwa OGC I
PDI-1 R/F S. Little ACRS DOCUMENT NAME: G:\\FITZWIA1764.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with att chment/ enclosure, "N" = No copy 0FFICE PM:PDI 1 f D' lE LA PDI 1 oV l
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August 31, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD BOLTING RELIEF REQUEST (TAC NO MA1764) l
Dear Mr. Knubel:
On May 8,1998, the New York Power Authority (also known as the Power Authority of the State of New York) submitted a request for relief from inservice inspection requirements for control rod bolting at the James A. FitzPatrick Nuclear Power Plant. The NRC staff, with the assistance of its contractor, INEEL, has determined that additional information will be required to complete its review of this relief request. The information required is described in the enclosure to this letter.
To expedite the review process, please provide a copy of your response directly to INEEL at the following address:
MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 ldaho Falls, Idaho 83415-2209 As discussed with Mr. Art Zaremba on August 27,1998, please provide the requested information by September 14,1998. If you have any questions regarding this matter, please contact me at (301) 415-1470.
Sincerely, a
i Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - t/11
(
Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Request for Additional Information cc w/ encl: See next page l
L
3 James Knubel James A. FitzPatrick Nuclear l
Power Authority of the State Power Plant L
of New York cc:
Mr. Gerald C. Goldstein Regional Administrator, Region I Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President l
New York State Energy, Research, Resident inspector's Office and Development Authority U. S. Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington Avenue Extension Lycoming, NY 13093 Albany, NY 12203-6399 Mr. Harry P. Salmon, Jr.
Mr. Richard L. Patch, Director Vice President - Engineering Quality Assurance Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street l
White Plains, NY 10601 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering l
Director Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of New York l
123 Main Street Mr. James Gagliardo White Plains, NY 10601 Safety Review Committee 708 Castlewood Avenue Supervisor Arlington,TX 76012 Town of Scriba Route 8, Box 382 Mr. Arthur Zaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41 President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State Mr. Paul Eddy of New Yo*
New York State Dept. of 99 Washington Ave., Suite No. 2005 Public Service Albany, NY 12210-2820 3 Empire State Plaza,10th Floor Albany, NY 12223 Charles Donaldson, Esquire Assistant Attomey General Michael J. Colomb New York Department of Law Site Executive Officer j
120 Broadway James A. FitzPatrick Nuclear Power Plant j
New Yo&, NY 10271 P.O. Box 41 i
Lycoming, NY 13093
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS Raouest for Additional Information (RAI) on the Third 10-Year Intemal inservice insoection (ISI)
Request for Authonzation RR-14 1.
Scope / Status of Raving Throughout the service life of a water-cooled nuclear power facility,10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice inspection of Nuclear Power Plant l
Components," to the extent practical within the limitations of design, geometry, and materials of l
construction of the components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during successive 120-month l
inspection intervals comply with the requirements in the latest edition and addenda of the Code l
incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the j
interval, subject to the limitations and modifications listed therein. The components (including l
supports) may meet examination requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval. The licensee, New York Power Authority, prepared the James A. FitzPatrick Nuclear Power Plant third 10-year interval program plan to meet the requirements of the 1989 Edition of the ASME Code Section XI. The third 10-year interval began in June 1997.
As required by 10 CFR 50.55(g)(5), if the licensee determines that certain Code examination requirements are impractical and requests relief, the licensee shall submit information to the NRC to support that determination.
i The staff has reviewed the available information for Request for Rclief No. RR-14, submitted l
May 8,1998. Based on this review, the staff has concluded that the information and/or
. clarification described in the next section is required to complete the review of the licensee's request.
l 2.
AddlitonalInformation Required a.
Request for Relief No. RR-14 seeks relief from the additional examination requirements of lWB-2430 for control rod drive (CRD) housing bolts. However, the licensee has net l
established the burden of performing these examinations in accordance with 10 CFR 50.55a(a)(3)(ii). In addition, the licensee has not explained how the proposed altemative, to replace existing bolting with bolts of a new design, will provide an acceptable level of quality and safety.
Part of the basis for relief explains that replacing all of the remaining 73 CRD mechanism
. bolts would result in approximately 18 person-rom exposure. It appears that this exposure will be accrued regardless of the time frame necessary to complete the replacement of all the bolting. Furthermore, replacing existing cracked bolts with ones of the new design does Enclosure l
l l ~ to 2-I i
not provide reasonable assurance that the structuralintegrity of the remaining bolts (those in the expanded examination sample) will be maintained. Have crack propagation rates for l
existing cracked bolts been established? What is the schedule for completion of CRD mechanism bolt replacement? Provide information to support the licensee's position that
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the additional examinations either create a hardship, or that the proposed attemative will provide an acceptable level of quality and safety..
I b.
The licensee has described a course of action for replacement of existing CRD bolting with I
bolts of a new design. It is stated in the Altemate Examination that "the new design bolts may be re-used after a W-1 and augmented surface examination determines that there are no relevant indications." However, the licensee's intentions regarding additional examinations for the new bolting is not clear. Additional examinations for the new bolting should be performed as required by the Code unless otherwise justified. Clarify the scope l
of this request regarding additional examinations to IWB-2430 and bolts of the new design that do not meet the acceptance criteria of IWB-3517.
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